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You searched for: mediatype:texts AND collection:ufgdp AND subject:"Neutron Transport Theory"		Advanced search
[texts]Thermal neutron flux in the Argonne heavy-water pile - Argonne National Laboratory
http://uf.catalog.fcla.edu/uf.jsp?st=UF005023929&ix=nu&I=0&V=D&pm=1
Keywords: Thermal neutrons; Nuclear fission; Neutron transport theory; Nuclear reactors
Downloads: 52
[texts]Calculation of neutron distributions in heterogeneous piles - Clinton Laboratories
http://uf.catalog.fcla.edu/uf.jsp?st=UF005023931&ix=nu&I=0&V=D&pm=1
Keywords: Neutrons; Nuclear fission; Slow neutrons; Neutron cross sections; Neutron transport theory
Downloads: 53
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